EP2180483A1 - Verfahren zur hemmung der adhäsion einer radioaktiven substanz und vorrichtung mit gehemmter adhäsion damit - Google Patents

Verfahren zur hemmung der adhäsion einer radioaktiven substanz und vorrichtung mit gehemmter adhäsion damit Download PDF

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Publication number
EP2180483A1
EP2180483A1 EP08827827A EP08827827A EP2180483A1 EP 2180483 A1 EP2180483 A1 EP 2180483A1 EP 08827827 A EP08827827 A EP 08827827A EP 08827827 A EP08827827 A EP 08827827A EP 2180483 A1 EP2180483 A1 EP 2180483A1
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EP
European Patent Office
Prior art keywords
substance
adhesion
radioactive substance
suppressing
metallic material
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
EP08827827A
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English (en)
French (fr)
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EP2180483A4 (de
EP2180483B1 (de
Inventor
Seiji Yamamoto
Masami Enda
Hiromi Aoi
Yutaka Uruma
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Toshiba Corp
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Toshiba Corp
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Publication date
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Publication of EP2180483A1 publication Critical patent/EP2180483A1/de
Publication of EP2180483A4 publication Critical patent/EP2180483A4/de
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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/08—Vessels characterised by the material; Selection of materials for pressure vessels
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/16—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants comprising means for separating liquid and steam
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G21C17/0225—Chemical surface treatment, e.g. corrosion
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/307—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the present invention relates to a method and an apparatus for suppressing the adhesion of radioactive substance onto the surface of metallic materials in structural members of a nuclear plant.
  • the measure for reduction of radioactive exposure dosage to workers during periodical inspection works, a preventive maintenance construction, etc. is important.
  • a chemical decontamination is frequently applied to structural members of the nuclear reactor (such as a reactor pressure vessel, an intra-furnace structure) and piping.
  • oxide films formed in the surface of metallic materials in structural members of the nuclear reactor and piping are removed by combining reduction and oxidation processes, etc., using chemicals, thereby removing radioactive substances, such as cobalt 60 and cobalt 58 existing in the clad or oxide film on the surface of a metallic material.
  • Patent document 1 proposes to alternately repeat the injection of an oxidizing agent and a reducing agent to the instrument and piping of a nuclear power generation plant so as to form an oxide film on the metal material surface of the above-mentioned instrument or piping after decontamination, thereby suppressing adhesion of a radioactive substance.
  • Patent document 2 It is further known to have hot oxygen or ozone contact the piping of a residual heat removal system after decontamination to form an oxide film on the piping surface, thereby suppressing adhesion of a radioactive substance.
  • Patent document 3 It is also known to have a chemical containing iron ion contact the surface of metal members constituting a nuclear plant to form a ferrite film on the surface, thereby suppressing adhesion of a radioactive substance.
  • Patent document 4 titanium oxide is used as a catalytic substance.
  • Patent document 4 reduces corrosion potential by a pn junction of the oxide film and the catalytic substance, thereby realizing the suppression of a stress corrosion cracking development, and it does not aim at suppressing the adhesion of a radioactive substance.
  • an object of the present invention is to provide a method and an apparatus for suppressing radioactive substance, by which adhesion of radioactive substance onto the surface of the metallic materials forming structural members of a nuclear plant can be suppressed.
  • the method of suppressing adhesion of radioactive substance comprises: disposing a material containing a titanium compound as a substance for suppressing adhesion of radioactive substance on a surface of a metallic material forming a structural member of a nuclear plant, and holding the material at 80 °C or higher.
  • the present invention also provides an apparatus for suppressing adhesion of radioactive substance, comprising: a structural member comprising a metallic material having a surface in a nuclear power generation plant, and a layer of substance for suppressing adhesion of radioactive substance containing a titanium compound and disposed on the surface of the metallic material, so that the structural member is in contact with primary cooling water for a nuclear reactor via the layer of the substance for suppressing adhesion of radioactive substance.
  • the incorporation or take-in of the radioactive substance to the inside of the oxide film formed on the surface of the above-mentioned metallic material is inhibited with the substance inhibiting adhesion of radioactive substance disposed on the surface of the metallic material forming the structural member of a nuclear plant, whereby adhesion of the radioactive substance to the surface of the metallic material can be suppressed.
  • Fig. 1 is a flow diagram showing a primary cooling water system for a boiling water reactor, to which a first embodiment of the radioactive substance-adhesion suppression method and apparatus of the present invention is applied.
  • Fig. 2 is a sectional view showing a portion of a pipe which is a structural member in a nuclear power generation plant as shown in Fig. 1 .
  • a boiling water reactor 10 in a nuclear power generation plant is provided with a primary cooling water system including a main steam system 11, a recycled water supply system 12, a nuclear reactor recirculation system 13, a residual heat removal system 14, and a nuclear reactor coolant purification system 15, etc.
  • the boiling water reactor 10 includes a reactor pressure vessel 16 and a core 17 accommodated in the vessel 16.
  • the main steam system 11 supplies steam generated in the reactor pressure vessel 16 through the main steam system pipe 18 to a steam turbine (not shown).
  • steam having worked after being sent to the steam turbine is condensed by a condenser (not shown) to form a recycled water, which is then recycled to the reactor pressure vessel 16 through a recycled water supply system pipe 20 equipped with a feed pump 19 and a feed water heater (not shown).
  • the nuclear reactor recirculation system 13 forcibly sends cooling water (coolant) into the reactor core 17. More specifically, the nuclear reactor recirculation system 13 includes a plurality of jet pumps 22 disposed in a downcomer part between a reactor core shroud 21 disposed so as to surround the reactor core 17 and the reactor pressure vessel 16, and recycle system pumps 24 disposed in re-circulation system piping 23 for elevating the pressure of the cooling water withdrawn out of the reactor pressure vessel 16. In the nuclear reactor recirculation system 13, the cooling water, of which the pressure was elevated by the re-circulation system pumps 24, is led to the jet pumps 22 which suck the cooling water therearound and forcibly send the cooling water into the lower part of the reactor core 17.
  • the residual heat removal system 14 includes residual heat removal system piping 25 connected to a position upstream of the re-circulation system pump 24 in the re-circulation system piping 23, and a residual heat removal system pump 26 and a heat exchanger 27 disposed in the residual heat removal system piping 25.
  • the cooling water led to the residual heat removal system piping 25 from the nuclear reactor recirculation system 13 is cooled by the heat exchanger 27 and led to the reactor pressure vessel 16.
  • the nuclear reactor coolant purification system 15 includes coolant purification system piping 28 connected to a position upstream of the residual heat removal system pump 26, and a heat exchanger 29, a coolant purification system pump 30 and a filtration demineralizer 31 disposed in the coolant purification system piping 28.
  • the cooling water (coolant) led to the coolant purification system piping 28 from the nuclear reactor recirculation system 13 is cooled by the heat exchanger 29 and led to and purified by the filtration demineralizer 31, and the purified cooling water is led to the recycled water supply system piping 20.
  • the structural members in the nuclear power generation plant including, e.g., the reactor pressure vessel 16; intra-reactor structure, such as the reactor core shroud 21 and the jet pump 22; intra-reactor instruments (such as a gas-water separator and steam drier); and the instruments, such as pumps, and piping in the primary cooling water system (including the main steam system 11, the recycled water supply system 12, the nuclear reactor recirculation system 13, the residual heat removal system 14, and the nuclear reactor coolant purification system 15), are exposed to hot cooling water containing radioactive substance, so that oxide films having taken radioactive substance therein are formed on the surfaces of metallic materials forming the structural members.
  • the incorporation or take-in of radioactive substance into this oxide film is inhibited to suppress adhesion of the radioactive substance onto the surfaces of the above-mentioned metallic materials.
  • a pipe 32 shown in Fig. 2 is a structural member (forming a part of piping in the primary cooling water system) in a nuclear power generation plant, and primary cooling water (simply called “cooling water” hereafter) of the boiling water reactor 10 flows through inside thereof.
  • the pipe 32 is composed of a metallic material, such as stainless steel, and an oxide film 33 is formed on the surface (inner surface) of the pipe 32.
  • a solution or a suspension (a suspension in a particular example) of an adhesion-suppressing substance 34 capable of inhibiting adhesion of radioactive substance 36 (mentioned later) is sprayed so as to adhere onto the surface of the oxide film 33, thereby forming a layer of the adhesion-suppressing substance 34.
  • the adhesion-suppressing substance 34 is a substance containing titanium oxide as a titanium compound.
  • the adhesion-suppressing substance 34 is preferably formed in a layer on the entire surface of the oxide film 33 but can be formed discretely on the surface of the oxide film 33.
  • a portion having the adhesion-suppressing substance 34 is held at 80 °C or higher within air, steam or water to enhance the tightness of the adhesion-suppressing substance 34, especially titanium oxide, and also enhance the adhesion of the adhesion-suppressing substance 34 onto the oxide film 33.
  • the pipe 32 After being provided with the adhesion-suppressing substance 34, the pipe 32 is use in operation.
  • the pipe 32 as a structural member in a nuclear power generation plant contacts primary cooling water in the nuclear reactor via the oxide film 33 and the adhesion-suppressing substance 34 or via at least the adhesion-suppressing substance 34.
  • the pipe 32 contacts hot cooling water (nuclear reactor cooling water) 35, whereby the oxide film 33 grows and corrosion of the pipe 32 advances.
  • the cooling water 35 contains radioactive substance 36, such as cobalt 60.
  • radioactive substance 36 is taken into the oxide film 33 along with advance of the corrosion of the pipe 32.
  • the take-in of the radioactive substance 36 to the oxide film 33 is inhibited by the formation of the adhesion-suppressing substance 34 in a tight layer as mentioned above regardless of advance of the corrosion of the pipe 32.
  • Fig. 3 shows the results of a test wherein test pieces of SUS316L were immersed in water at 280 °C to form an oxide film thereon, and then immersed in water at 280 °C containing cobalt 60 for 500 hours.
  • the amount of adhered radioactive substance (cobalt 60) on a test piece coated with a titanium oxide could be reduced to about a half of the amount on a test piece with no titanium oxide (denoted by B in Fig. 3 ).
  • the take-in of radioactive substance 36 e.g. cobalt 60
  • adhesion of radioactive substance onto the surface 32A of the pipe 32 can be suppressed.
  • Fig. 4 is a sectional view showing a portion of a pipe for illustrating a second embodiment of the radioactive substance-adhesion suppression method and apparatus of the present invention.
  • parts identical to those in the first embodiment are denoted by identical numerals and explanation thereof is simplified or omitted.
  • This embodiment differs from the above first embodiment in that an oxide film 33 formed on the surface 32A of a pipe 32 is removed by a chemical decontamination treatment before spraying the suspension of an adhesion-suppressing substance 34.
  • the oxide film 33 formed in the surface 32A of the pipe 32 is first removed by a chemical decontamination treatment.
  • the chemical decontamination treatment is a treatment including at least one time of reductive dissolution or oxidative dissolution with a chemical, or at least one time of alternation of the above-mentioned reductive dissolution and oxidative dissolution.
  • the adhesion-suppressing substance 34 containing titanium oxide is deposited on the surface 32A of the pipe 32 from which the oxide film 33 has been removed by the above-mentioned chemical decontamination treatment. Also in the case, the adhesion-suppressing substance 34 may be formed over the entire surface 32A of the pipe 32, or discretely on the surface 32A by spraying a suspension of the adhesion-suppressing substance 34.
  • a portion having the adhesion-suppressing substance 34 is held at 80 °C or higher within air, steam or water to enhance the tightness of the adhesion-suppressing substance 34, especially titanium oxide, and also the adhesion of the adhesion-suppressing substance 34 onto the oxide film 33.
  • the pipe 32 After being provided with the adhesion-suppressing substance 34, the pipe 32 is used in operation, and contacts hot cooling water 35 to be corroded, whereby an oxide film 33 is formed between the adhesion-suppressing substance 34 and the surface 32A of the pipe 32. Also in this case, however, the take-in of the radioactive substance 36 to the oxide film 33 formed on the surface 32A of the pipe 32 is suppressed by the formation of the adhesion-suppressing substance 34 compared with a case where the adhesion-suppressing substance 34 is absent.
  • Fig. 5 shows the results of a test wherein test pieces of SUS316L were immersed in water at 280 °C to form an oxide film thereon, subjected to removal of the oxide film by chemical decontamination and then immersed in water at 280 °C containing cobalt 60 for 500 hours.
  • the amount of adhered cobalt 60 onto a test piece having removed the oxide film was increased to two times or more compared with the case of retaining the oxide film (denoted by B in Fig. 3 ).
  • the amount of adhered cobalt 60 on a test piece provided with titanium oxide could be reduced to about 1/5 of the amount on a test piece with no titanium oxide (denoted by D in Fig. 5 ).
  • the take-in of radioactive substance 36 e.g. cobalt 60
  • adhesion of radioactive substance 36 onto the surface 32A of the pipe 32 can be suppressed.
  • this embodiment has been described with respect to the case where the oxide film 33 is removed from the surface 32A of the pipe 32, a similar effect is expectable even if this embodiment is applied to a pipe having no oxide film from the outset, like a fresh pipe.
  • the third embodiment differs from the first and second embodiments described above in that the radioactive substance adhesion-suppression method is performed at the time of inspection of a nuclear reactor, for example, at the time of the periodical inspection of the boiling water reactor 10. Also in this embodiment, parts identical to those in the first and second embodiments are denoted by identical numerals and explanation thereof is simplified or omitted.
  • decontamination treatment such as a chemical decontamination treatment
  • the pipe 32 which is a structural member as described above in a nuclear power generation plant, and the oxide film 33 is removed from the surface 32A of the piping 32.
  • the pipe 32 from which the oxide film 33 has been removed is filled with cooling water 35, into which a suspension of the adhesion-suppressing substance 34 containing titanium oxide is injected.
  • the adhesion-suppressing substance 34 containing titanium oxide is deposited and formed on the surface 32A of the pipe 32.
  • the temperature of the cooling water 35 in the pipe 32 is held at 80 °C - 100 °C to enhance the tightness of the adhesion-suppressing substance 34, especially titanium oxide, and also enhance the adhesion of the adhesion-suppressing substance 34 (particularly titanium oxide) onto the oxide film 33.
  • the adhesion-suppressing substance 34 containing titanium oxide is formed on the surface 32A of the pipe 32 which is an example of the structural member in a nuclear power generation plant, and owing to the adhesion-suppressing substance 34, even if the pipe 32 is used in operation, the take-in of radioactive substance 36 (e.g., cobalt 60) to the oxide film 33 formed on the surface 32A of the pipe 32 can be inhibited. As a result, it becomes possible to suppress the adhesion of the radioactive substance 36 to the surfaces of the metallic materials of the above-mentioned structural members, such as the surface 32A of the pipe 32, exposed to primary cooling water or steam thereof in the boiling water reactor 10.
  • radioactive substance 36 e.g., cobalt 60
  • the fourth embodiment differs from the first to third embodiments described above in that the method and apparatus for suppressing adhesion of radioactive substance are operated during the time of start-up, stopping or operation of a nuclear reactor. Also in this embodiment, parts identical to those in the first and second embodiments are denoted by identical numerals and explanation thereof is simplified or omitted.
  • the apparatus system of Fig. 1 is provided with a 1st injection point 37 upstream of the feed pump 19 in the recycled water supply system piping 20, a 2nd injection point 38 downstream of the re-circulation-system-pump 24 in the re-circulation system piping 23, a 3rd injection point 39 downstream of the residual-heat-removal-system-pump 26 in the residual heat removal system piping 25, and a 4th injection point 40 downstream of the coolant purification system pump 30 and the filtration demineralizer 31 in the coolant purification system piping 28, respectively, as denoted by two point-and-dash lines.
  • a suspension of the adhesion-suppressing substance 34 containing titanium oxide is injected from at least one of the 1st injection point 37, the 2nd injection point 38, the 3rd injection point 39 and the 4th injection point 40 described above by means of an injection pump (not shown), etc. during the time of start-up, stopping or operation of the nuclear reactor 10.
  • the injected adhesion-suppressing substance 34 is injected into the cooling water of the primary cooling water system (the recycled water supply system 12, the nuclear reactor recirculation system 13, the residual heat removal system 14, or the nuclear reactor coolant purification system 15) in which a selected one of the injection points 37-40 exists, to reach all the primary cooling water systems including the boiling water reactor 10 along with the cooling water, and is caused to adhere and disposed on the surface 32A of those structural members, such as pipe 32, directly or via the oxide film 33.
  • the primary cooling water system the recycled water supply system 12, the nuclear reactor recirculation system 13, the residual heat removal system 14, or the nuclear reactor coolant purification system 15
  • the temperature of cooling water is controlled at 100 °C - 200 °C , so that the tightness of the adhesion-suppressing substance 34 disposed on the surface 32A of the pipe 32 directly or via the oxide film 33 is improved, and the adhesion to the surface 32A or the oxide film 33 of the pipe 32 is improved.
  • the adhesion-suppressing substance 34 is directly formed on the surface 32A of the pipe 32, in the case where the pipe 32 is a fresh pipe or the oxide film 33 has been removed by decontamination from the surface 32A of the pipe 32.
  • the adhesion-suppressing substance 34 containing titanium oxide is formed on the surface 32A of the pipe 32 which is an example of the structural member in a nuclear power generation plant, and owing to the adhesion-suppressing substance 34, the take-in of radioactive substance 36 (e.g., cobalt 60) to the oxide film 33 formed on the surface 32A of the pipe 32 can be inhibited. As a result, it becomes possible to suppress the adhesion of the radioactive substance 36 to the surfaces of the metallic materials of the above-mentioned structural members, such as the surface 32A of the pipe 32.
  • radioactive substance 36 e.g., cobalt 60
  • the present invention can also be applied to the improved type boiling water reactor (ABWR) equipped with an internal recycle system inside the reactor, and can also be applied to the pressurized water reactor (PWR) with a light water reactor.
  • ABWR improved type boiling water reactor
  • PWR pressurized water reactor
  • the reactor pressure vessel is replaced by a reactor vessel, and an intra-reactor structure, a core vessel, a control rod cluster, etc., are disposed in the reactor vessel.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)
  • Other Surface Treatments For Metallic Materials (AREA)
  • Chemical Treatment Of Metals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
EP08827827.0A 2007-08-23 2008-08-21 Verfahren zur hemmung der adhäsion einer radioaktiven substanz Active EP2180483B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
JP2007217541 2007-08-23
PCT/JP2008/064940 WO2009025330A1 (ja) 2007-08-23 2008-08-21 放射性物質の付着抑制方法およびその付着抑制装置

Publications (3)

Publication Number Publication Date
EP2180483A1 true EP2180483A1 (de) 2010-04-28
EP2180483A4 EP2180483A4 (de) 2012-07-25
EP2180483B1 EP2180483B1 (de) 2014-06-04

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EP08827827.0A Active EP2180483B1 (de) 2007-08-23 2008-08-21 Verfahren zur hemmung der adhäsion einer radioaktiven substanz

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US (1) US20110122986A1 (de)
EP (1) EP2180483B1 (de)
JP (1) JPWO2009025330A1 (de)
ES (1) ES2478013T3 (de)
TW (1) TWI401699B (de)
WO (1) WO2009025330A1 (de)

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KR101278231B1 (ko) * 2009-05-29 2013-06-24 가부시끼가이샤 도시바 방사성 물질 부착 억제 방법 및 시스템
JP5774285B2 (ja) * 2010-06-25 2015-09-09 株式会社東芝 ジェットポンプの皮膜形成方法
JP2014182020A (ja) * 2013-03-19 2014-09-29 Toshiba Corp 放射性物質付着抑制方法
WO2023077672A1 (zh) * 2021-11-05 2023-05-11 中广核研究院有限公司 核反应装置及净化系统

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EP2180483B1 (de) 2014-06-04
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TW200926205A (en) 2009-06-16
TWI401699B (zh) 2013-07-11
WO2009025330A1 (ja) 2009-02-26
US20110122986A1 (en) 2011-05-26
JPWO2009025330A1 (ja) 2010-11-25

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